ProgramMaster Logo
Conference Tools for 2025 TMS Annual Meeting & Exhibition
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Abstract
Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Special Topics in Nuclear Materials: Lessons Learned; Non-Energy Systems; and Coupled Extremes
Presentation Title Best Practices for Irradiation Experiment Design For Nuclear Fuels and Materials Research
Author(s) Richard Howard
On-Site Speaker (Planned) Richard Howard
Abstract Scope Irradiation experiments are critical for advancing the understanding of nuclear material and fuel performance. However, designing such tests require stakeholders to interface with multiple groups (material scientists, irradiation facilities, experiment designers, etc.) to successfully deploy a successful experiment. Furthermore, irradiations experiment outcomes are generally not one-off activities but rather accumulate to extend the state of the art. As such, the work spans beyond experiment goals (i.e. separate vs. integral effects), irradiation facilities, and researcher careers. Therefore, establishing best practices for designing irradiation experiments is imperative to demonstrate efficiency, parity, and cohesion among the diverse experimentation efforts. This work describes such practices for irradiation experiment design to ensure the successful advancement of nuclear materials and fuels and suggests areas where the research community can improve the execution of this vital work.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials,

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advancing Radioisotope Heat Sources: Enhancing RPS for Extreme Environments
Atomistic Simulation of Thermal and Irradiation Creep Mechanisms in BCC-Fe and FCC-Ni using Defect Rate-Based Long-time Dynamics
Best Practices for Irradiation Experiment Design For Nuclear Fuels and Materials Research
Cavity Formation Induced by Swift Heavy Ion Irradiation in AlN/GaN
Comparison of Hardening and Microstructures of Structural Alloys Irradiated with Fast Neutrons and Dual Ions
Developing a High-Performance Cluster Dynamics Code: Challenges and Lessons Learned
Effect of Applied Stress on Radiation-Induced Loop and Raft Formation in a BCC Metal
Effect of Tensile Stress Gradients on the Multi-Length-Scale Microstructure in Thermal and Irradiation Creep of 316L Stainless Steel
Energy Dispersive X-Ray Spectroscopy (EDS) Induced Defects and Implantation Induced Impurities in Uranium Nitride (UN) and SIMFUEL Pellets
Fabrication of Titanium-Containing Tri-Carbide Ultra-High Temperature Ceramics
GIRAFFE – In Situ Material TestsUnder Fusion-Relevant Conditions
In-situ Electron Microscopy Characterization of Deformation Mechanisms of Inconel 718 Irradiated with Simultaneous High Energy Protons and Spallation Neutrons
Influence of Radiation Swelling on Residual Stresses and Measurement of Micromechanical Properties
Materials Research for High-Power Accelerator Beam-Intercepting Devices
Modeling Galvanic Drawdown Separations Technique
Phase Field Modeling of Irradiation-Induced Amorphous-to-Crystalline (A-C) Transformations in Structural Ceramics
Post Irradiation Examination and Administrative Lifetime Limits of Highly Irradiated Components at The Spallation Neutron Source
Small Scale Tests, Big Lessons Learned
The Recovery of Irradiation Damage for Zircaloy-2 and Zircaloy-4 following Irradiation at Higher Temperatures of 377-410°C

Questions about ProgramMaster? Contact programming@programmaster.org